curated documents pertaining to early molten salt reactor research.
☆27Mar 7, 2024Updated last year
Alternatives and similar repositories for msr-archive
Users that are interested in msr-archive are comparing it to the libraries listed below
Sorting:
- detailed cad model of the msre☆42Oct 29, 2025Updated 4 months ago
- Repository for Moltres, a code for simulating Molten Salt Reactors☆78Updated this week
- A package for Modelica simulating Molten Salt Reactors☆20Aug 6, 2016Updated 9 years ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆43Dec 24, 2025Updated 2 months ago
- DRAGON V5 reactor physics code workshop with useful scripts and examples☆12Aug 4, 2025Updated 7 months ago
- A tool for making reproducible materials and standardizing use across several neutronics codes☆25Oct 1, 2024Updated last year
- Converts CAD file(s) such as STP and SAT to a h5m file compatible with DAGMC based simulations using the Cubit Python API☆11Oct 11, 2023Updated 2 years ago
- OpenMC Workshop for Canadian Nuclear Laboratories☆12Mar 17, 2017Updated 8 years ago
- Three-Dimensional Discrete Ordinates Neutron, Photon, Electron and Positron Transport Code☆12Feb 26, 2022Updated 4 years ago
- Repository for running SINBAD benchmarks with OpenMC and UQ☆10May 18, 2022Updated 3 years ago
- Catalogs a plethora of reactor inputs for OpenMC☆36Feb 28, 2025Updated last year
- This repository holds codes from the book Computational Nuclear Engineering and Radiological Science with Python☆16Jul 9, 2020Updated 5 years ago
- Holds the research group website.☆13Feb 13, 2026Updated 3 weeks ago
- Simulate PWR,CANDU and VVER reactor (Assembly Model) using OpenMC https://openmc.readthedocs.io/en/stable/☆14Nov 29, 2019Updated 6 years ago
- MC/DC: Monte Carlo Dynamic Code☆52Feb 27, 2026Updated last week
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆18Dec 11, 2025Updated 2 months ago
- An open-source nuclear reactor analysis automation framework that helps design teams increase efficiency and quality☆262Updated this week
- Native plotting GUI for model design and verification☆65Feb 9, 2026Updated 3 weeks ago
- Nuclear data processing with legacy NJOY☆124Jan 20, 2026Updated last month
- Collection of scripts for managing data for OpenMC☆39Dec 23, 2025Updated 2 months ago
- ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…☆42Dec 11, 2024Updated last year
- OpenMC wrapped as a Moose App☆16May 1, 2023Updated 2 years ago
- A C++ Monte Carlo Neutron Transport Code☆20Dec 10, 2025Updated 2 months ago
- High-Fidelity Multiphysics☆130Feb 19, 2026Updated 2 weeks ago
- A curated list of open source projects used in nuclear science and engineering☆448Feb 4, 2026Updated last month
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆43Jun 25, 2024Updated last year
- A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak☆19Sep 13, 2021Updated 4 years ago
- Nuclear Reactor Theory☆20Nov 9, 2017Updated 8 years ago
- PyNE: The Nuclear Engineering Toolkit☆312Oct 22, 2025Updated 4 months ago
- Machine learning and artificial intelligence benchmarking library for nuclear engineering applications.☆29May 19, 2025Updated 9 months ago
- The main whatisnuclear.com website☆34Feb 21, 2026Updated last week
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆32Jan 29, 2026Updated last month
- ☆33Jul 21, 2025Updated 7 months ago
- Open Nuclear Reactor Simulator☆72Apr 25, 2025Updated 10 months ago
- Simulation of transmutation and decay in nuclear systems☆35Feb 21, 2026Updated last week
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆38Jul 3, 2025Updated 8 months ago
- Method of Characteristics neutral particle transport code for reactor physics written in Julia.☆28Jul 10, 2023Updated 2 years ago
- An Open Nuclear Reactor Simulator and Reactor Core Analysis Tool☆28Jan 9, 2021Updated 5 years ago
- OpenMC Monte Carlo Code☆975Updated this week